共 44 条
- [41] Comparison of neutron transport calculation methods based on C5G7-MOX and preliminary analysis of sensitivity of MOC parameters He Jishu/Nuclear Techniques, 2024, 47 (10):
- [42] Progress in Development of High-fidelity 3D Neutron Transport Calculation Code for Reactor Core Based on Heterogeneous Architecture Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022, 56 (02): : 285 - 295